Study and Design of Two-Phase Flow Experiment Loop in a Rectangular Mini-Channel

被引：0
|
作者：
Zhang J. [1 ]
Chen H. [1 ]
Zhang X. [1 ]
机构：
[1] School of Physical Sciences, University of Science and Technology of China, Hefei
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2019年 / 40卷 / 06期
关键词：
Both-sides heated; Downward flow direction; Experimental loop design; NP engineering reactor; Rectangular narrow channel;
D O I：
10.13832/j.jnpe.2019.06.0035
中图分类号：
学科分类号：
摘要：
In order to study the flow and heat transfer characteristics of narrow rectangular coolant channels in plate-fuel reactors, the research status and development trend of the heat transfer in mini-channels around the world were reviewed. Based on the related parameters and experiment requirements of NP engineering reactors, a set of experimental loops for thermal hydraulic two-phase flow was established to study and analyze the heat transfer characteristics in plate-fuel cooling channels. According to real reactor operational requirements, a test section consistent with the actual coolant channel was designed. The flow direction is vertically downward, and the double-sided heating method is adopted, and the flow passage gap size is 2.3 mm. The channel width is 67 mm (62 mm-heated width), and the runner length is 1000 mm (750 mm-heated length). It was verified experimentally. The results show that the apparatus is correct and feasible. © 2019, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
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页码：35 / 39
页数：4
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